Number of hours
- Lectures 8.0
- Projects 0
- Tutorials 8.0
- Internship 0
- Laboratory works 0
- Written tests 0
ECTS
ECTS 2.0
Goal(s)
Introduction to one numerical method used in deterministic neutron transport codes : collision probabilities.
Understanding the industrial neutron calculation scheme.
Getting experience with the practical use of a deterministic neutron transport code for simplified reactor physics calculations.
Calculation of temperature coefficients, homogeneisation, fuel burn up calculations.
Contact Adrien BIDAUDContent(s)
Neutron Transport theory :
From transport to diffusion equation : assumptions and approximations.
Example of a transport solution method : Collision Probabilities.
Preparing diffusion cross section : energy condensation, flux-volume homogeneisation, transport-diffusion equivalence.
Fuel burn-up calculation.
Fuel management
Industrial calculation scheme
Prerequisites
- Reactor physicis : criticality, temperature feedbacks, fuel management
- Neutronics : slowing-down equation, resonance self-shielding, transport equation, diffusion model
- Numerical methods : PDEs, numerical quadrature methods, solving numerically linear systems.
Test
TD = Exercice session evaluation (3*10%)
projet = Simulation project : Fuel burn-up of simple fuel cells (70%)
Présentiel ou distanciel =
Contrôle continu : 3*10% non rattrapable
Projet = 70% rattrapable
Additional Information
This course brings 1.0 ECTS to students in UE Common core JUAS/ESIPAP (DD-S9)
This course brings 2.0 ECTS to students in TU Simulations
This course brings 1.0 ECTS to students in UE Common core
This course brings 1.0 ECTS to students in UE Simulations JUAS
Course list
Curriculum->Master->Semester 9
Curriculum->Double-Diploma Engineer/Master->Semester 9
Bibliography
DRAGON User Manual : TECHNICAL REPORT IGE–174 Rev. 12 (Release 3.06L)
"La Neutronique", Monographies CEA/DEN, 2013, ISBN 978-2-281-11371-6
Applied Reactor Physics, Alain Hebert, Presses internationales Polytechnique, 2009